ML16340B981
| ML16340B981 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon |
| Issue date: | 08/04/1981 |
| From: | Mendonca M, Sternberg D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML16340B982 | List: |
| References | |
| 50-275-81-18, 50-323-81-12, NUDOCS 8109030068 | |
| Download: ML16340B981 (6) | |
See also: IR 05000275/1981018
Text
Report
No.
License
No.
50-275/81-18
'50-'323/81-12
<<275
50-323
Priority
CPPR-39
CPPR-69
Category
0
~
U. S.
NUCLEAR REGULATORY COMMISSION
OFFICE
OF INSPECTION AND ENFORCEMENT
REGION V
Licensee:
Pacific
Gas and Electric Company
PE 0 ~ Box 7442
San Francisco, California 94106
Facility Name:
Diablo Canyon Units 1 and
2
Inspection at:
Inspection conducted:
Inspectors:
July 3 - July 31,
1981
>i err/
ate Signed
Marvin Mendonca,
Resident
Reactor Inspector
Diablo Canyon Site,
San Luis Obispo County, California
Date Signed
Date Signed
Approved by:
D. M. Sternberg,
f,
eactor Pro)ects
Section
1
Date Signed
Summary:
Ins ection of Jul
3 to Jul
31
1981
Re ort Nos. 50-275/81-18
& 50-323/81-12
Areas Inspected:
Routine inspection including plant tours, fire prevention/
protection reviews, inspection of fuel storage facilities, and plant
procedure
reviews.
This inspection involved 46 inspector<<hours
onsite by
an
NRC resident inspector.
Results:
No items of noncompliance or deviations were identified.
IE:V Form 219
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8i09030068
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1.
Persons
Contacted
DETAILS
- R. Thornberry, Plant Manager
"R. Patterson,
Plant Superintendent
'~J.
S. Diamonon,
QC Supervisor
- J. M. Gisclon,
Power Plant Engineer
~ D.
Q. Backens,
Supervisor of Maintenance
~J. A. Sexton,,Supervisor
of Operations
~.J. V. Boots, Supervisor of Chemistry and Radiation Protection
- R. T. Twiddy, Supervisor of Quality Assurance
i'W. B. Kaefer, Technical Assistant to the Plant Manager
The inspector also talked with and interviewed
a number of other".licensee
employees
including members of general construction,
the operations staff,
and
QA personnel.
- Denotes those attending the exit interview.
2.
Plant Tour
The inspector walked through various areas of the plant on a weekly basis
to observe activities in progress;
to inspect the general state of clean-
liness,
housekeeping,
and adherence
to fire protection rules; to check the
proper approval of "man on the line, caution and clearance"
tags
on
equipment,
and to review with operations
personnel
the status of various
systems in the plant.
The inspector observed that the status of the systems
and the housekeeping
appeared
consistent with construction activities.
The reactor cavity is
still being maintained
as
a clean area.
No items
on noncompliance
or deviations were identified.
3.
Procedure
Review
Procedures
Reviewed:
EP';-'-4
STP M-9A
Emergency Procedure
Diesel Engine Generator
Routine Surveillance Test
No items of noncompliance
or deviations were identified.
4.
Fire Prevention/Protection
The control room and cable spreading
room were inspected.
The fire alarm,
extinguishing
equipment actuating controls and fire fighting equipment
were verified to be operable in the cable spreading
room and
25% of the
balance of the plant.
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The results of the latest fire inspections that were performed
by the
licensee
and its consultant
have been reviewed.
An audit of potential
fire hazards for vital areas
found that corrective actions
had been taken
or planned.
No items on noncompliance or deviations were identified.
5.
New Fuel Store
e
Units 1 & 2
The new fuel storage
and security was inspected.
The inspector verified
that the integrity of the security controls were being maintained
and
adequate
procedures
were available
and enforced.
Environmental protection
to control dust
and debris,
and to prevent fuel damage
was being maintained.
The inspection ascertained
that the requirements
of both special nuclear
materials licenses
were being met.
No items of noncompliance or deviations
were identified.
6.
Com arison of As-Built Plant to FSAR Descri tion
This is a status
report on the subject ongoing review topic.
To date this
review has considered
the high and intermediate
head safety injection
piping schematics.
The applicable sections of the FSAR have been reviewed
to establish
design
commitments.
System walk-downs determined that the
systems
were installed in agreement with drawing under quality control per
FSAR commitments.
Therefore,
by review of this FSAR and field observations,
the high and intermediate
head safety injection system mechanical
and
fluid design were verified in conformance with the FSAR.
No items of noncompliance or deviations were identified.
7.
Exit Interview
An inspector met with senior licensee
representatives
on a weekly basis
and
with the representatives
(denoted in Paragraph
1) on July 31, 1981.
The
scope
and findings of the inspection were summarized
by the inspector.
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